Adrien Bidaud

TL;DR: In this article, a collision history-based approach to sensitivity/perturbation calculations in the Monte Carlo code SERPENT is discussed, allowing the calculation of the effects of nuclear data perturbation on several response functions: the effective multiplication factor, reaction rate ratios and bilinear ratios (e.g., effective kinetics parameters).

TL;DR: In this paper, the authors used the surrogate reaction method to obtain the neutron-induced fission cross-sections for the first time up to the onset of second-chance fission.

TL;DR: In this paper, the conversion performance of thorium-fueled standard or only slightly modified CANDU and PWR reactors with unchanged core envelope and equipments, to be eventually used as the third and last tier of symbiotic scenarios, is investigated.

TL;DR: The status of the Joint Evaluated Fission and Fusion file (JEFF) is described in this paper, which comprises a significant update of actinide evaluations, materials evaluations that have emerged from various European nuclear data projects, the activation library JEFF-3.1/A, decay data and fission yield sub-libraries, and fusion-related data files from the EFF project.

TL;DR: In this article, the authors presented a methodology based on neural networks for building a fuel loading model and a cross section predictor for a PWR reactor loaded with MOX fuel, which allows completion of the fuel depletion calculation in less than one minute with excellent accuracy.